Analisis Integritas Struktur MenggunakanProgram MSC Software

Roziq Himawan

Pusat Teknologi Reaktor dan Keselamatan NuklirBadan Tenaga Nuklir Nasional

Pusat Teknologi Reaktor dan Keselamatan Nuklir

1. Bidang Fisika dan Teknologi Reaktor

2. Bidang Pengembangan Reaktor

3. Bidang Pengkajian Analisis Keselamatan Reaktor

4. Bidang Pengembangan Teknologi Keselamatan Nuklir

5. Bidang Operasi Fasilitas

Bidang Pengembangan Teknologi Keselamatan Nuklir

Melakukan kegiatan penelitian terkait dengan

1. Analisis Sistem Keselamatan Instalasi Nuklir

2. Analisis Keandalan Instalasi Nuklir

3. Pengembangan Budaya Keselamatan dan Ergonomika

Analisis Keandalan Instalasi Nuklir

Melakukan Litbang integritas struktur untuk menjamin keselamatan reaktor

Desain Struktur suatu Reaktor PWR

Desain Struktur Sistem PendinginPrimer PWR

Fasilitas untuk Analisis Integritas Struktur

Perangkat keras (Mesin Uji Mekanik)1. Mesin Uji Tarik Universal2. Mesin Uji Tarik Dinamik (Fatik)3. Mesin Uji Creep4. Mesin Uji Impak (Charpy)5. Alat uji metalografi6. Berbagai alat uji NDT

Fasilitas untuk Analisis Integritas Struktur

Perangkat Lunak1. MSC Patran → FEM Computer Code Biasa2. MSC Fatigue → Analisis disain fatik3. MSC Marc → Non-linier analysis4. MSC Multi Discipline5. Caesar II → Piping Stress 6. Catia7. Item Tool Kit → Software analisis keandalan8. Software analisis Human Factor

MSC Fatigue

MSC FatigueResults :

1. Life Estimation2. Log of Life3. Damage4. Component Specific Life Unit5. Factor or Safety6. Multiaxiality Indicators

MSC Marc

1. Geometric Nonlinearity ● Structural Instability and Collapse

● Large deflections ● Large rotations ● Preloads

MSC Marc

2. Contact Nonlinearity ● Rigid Body Contact ● Deformable body contact ● Contact with friction

MSC Marc

3. Material Nonlinearity ● Plasticity ● Progressive failure ● Creep

MSC MultiDiscipline

1. Motion-structural Mechanics2. Systems and Control3. Thermal Mechanical4. Multiphysics5. Implicit-Explicit-Implicit6. Fluid-Structure Interaction

Pemanfaatan dalam PLTN

1. Structural analysis of nuclear core support structures and concrete containment structures.2. Structural analysis of mechanical components and equipment : Pressure vessels, pumps, valves, piping systems and storage Tanks.3. Vibration analysis of equipment and components4. Drop testing of nuclear waste disposal casks5. Impact analysis of critical systems from fragments due to Accidental explosions6. Blast analysis of structural systems due to bomb blast7. Impact analysis of exterior structures due to acts of terorisms

Hasil Analisis untuk Komponen Reaktor

Gambar Bottom Head Instrument Penetration dan Model 2D

Hasil Analisis untuk Komponen Reaktor

Reactor Reactor CoreCore

NeutronNeutron

Non-ductile fracture must be avoided.Deterministic analysis method is prescribed in

Codes/Standards.

ECCS Water Injection

High Stress due to Pressure and Rapid Cooling

Fracture Toughness Degradation due to Neutron

Irradiation

In-service Inspection(non-detection probability)

RPV

PTS

Temp.

Inside Outside

Stress at Crack Tip

Vessel Wall

Cold E

CC

S W

ater Fracture T

oughness

KI,KIc

Temperature at crack tip

KI histories analyzed through a PTS transient

An axial crack having 10mm depth and 60mm length is assumed in RPV wall.

(Japanese procedure)

Fracture Toughness (KIc) > Stress Intensity Factor (KI)

Regulations require that the fracture toughness is maintained in an enough level throughout the plant operation.

In addition to the prediction of fracture toughness decrease, ∆RTNDT have to be monitored by the surveillance tests during plant operation.

Safety Margin

Initial (Unirrad.) KIc

KI

40 years operation

60 years

∆RTNDT

Terima kasih atas perhatian anda

roziqh@batan.go.id